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Status of plant assistance irradiations as of July 16, 1965

Description: This report covers the activities with regard to on-site customer irradiations as of the above date. The report covers the status of materials undergoing irradiation, awaiting disposition, material shipped during the month, and current status of all reactor test holes. The integrated exposure values are calculated in accordance with HW-62781, {open_quotes}Status Report Equations.{close_quotes} The integrated exposure reported is the average exposure received by the surrounding uranium columns. … more
Date: August 3, 1965
Creator: Ferguson, J. H.
Partner: UNT Libraries Government Documents Department
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K Area Hot Test Hole Temperatures

Description: This report details a K area test with the following objectives: find the temperature range within a graphite sample carrier; find the temperature range with a solid graphite bar; find the temperature range with a test hole; determine the temperature difference between the old and new graphite sample boats; compare the temperature of a sample load and a solid bar in the same location; and find the temperature range in which the graphite samples are irradiated in all test holes. Results and conc… more
Date: August 4, 1965
Creator: Cox, J. H.
Partner: UNT Libraries Government Documents Department
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Tritium extraction facility study - 1965

Description: This study was prepared in support of AEC-requested reactor case studies. Two of the cases include local separation and purification of tritium from Hanford irradiated aluminum-lithium alloyed slugs after 1974, at which time, the Savannah River Plant would be shut down. Consideration is given to processing N Reactor rods or {open_quotes}K{close_quotes} Reactor I&E slugs. Quantities of tritium to be produced would be five kilograms per year in one case and seven kilograms per year in the other c… more
Date: August 20, 1965
Creator: Kesel, G. P. & Wodrich, D. D.
Partner: UNT Libraries Government Documents Department
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Blisters in BDF-type control rods: Engineering final summary report

Description: The scope of this report defies a concise abstract. In lieu of an abstract, the following topical outline will both indicate the subjects covered and show how these subjects are organized. Part I, Engineering Aspects: Blister Formation, Temperature Effects, Cooling Effects, Drive Connections, Housing Effects, Housing Materials, Radiation Effects. Part II, The Behavior of Boron Carbide-Aluminum Poisons: Swelling, Swelling Rates, Restraint, Material Behavior.
Date: August 30, 1965
Creator: Riedeman, G. W.
Partner: UNT Libraries Government Documents Department
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Fuel element development committee annual report from Hanford

Description: This annual report details activities of the Fuel Element Development Committee. A summary of Hanford Atomic Products Operation activities is provided along with programs and performance of K, small reactor, and N-Reactor fuels.
Date: August 18, 1965
Creator: Lewis, M.; Minor, J. E. & Stringer, J. T.
Partner: UNT Libraries Government Documents Department
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Nuclear safety specifications for N-Reactor fuels for 2.4 w/o enriched uranium oxide fuel

Description: This specification covers the processing of a pilot lot of 2.4 w/o uranium oxide fuel in the N-Reactor Fuels facilities for the period from August 16, 1965, through March 1, 1966. A maximum of 180 fuel pieces will be processed. The fuel will be processed or stored in 306, 333, and 3,715 Buildings. Processing steps will include end closure welding, support and locking clip welding, final etching, autoclaving, final inspection, and assembly. Shipment to 100-N Area and from 325 Building are also c… more
Date: August 16, 1965
Creator: Black, B. R.
Partner: UNT Libraries Government Documents Department
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Physics and Instruments Department Monthly Report, July 1965

Description: This monthly document details activities of the Battelle-Northwest Physics and Instruments Department during the month of July 1965. (FI)
Date: August 15, 1965
Creator: Paul, R. S.
Partner: UNT Libraries Government Documents Department
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RADIATION PROTECTION DEPARTMENT REPORT FOR AUGUST 1965 BNWC-8-8-F

Description: This monthly report addresses developments in departmental organization, laboratory experience, environmental evaluation, nuclear safeguards, dosimetry studies, radiological development, environmental studies, and outside consultations.
Date: August 1, 1965
Creator: Keene, A. R.
Partner: UNT Libraries Government Documents Department
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Horizontal control rod renovation program all production reactors

Description: The purpose of this document is to outline the proposed implementation of engineering program results to remedy the major horizontal control rod (HCR) problems at Hanford production reactors. K and C Reactors currently use a water cooled, round, aluminum control rod packed with boron carbide powder, B and D Reactors use a water cooled, flat, aluminum rod made up of sintered boron carbide-aluminum rings strung on three cooling tubes, all of which is encased in an outer aluminum shell. The nature… more
Date: August 23, 1965
Creator: Hutton, P. H.
Partner: UNT Libraries Government Documents Department
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U-10 Wt % Mo Fuel Element: Irradiation in SRE

Description: From abstract: The fuel element assembly was successfully irradiated in the SRE to a maximum burnup of 5300 Mwd/MTU, at a peak fission rate of approximately 1.5 x 10E13 fissions/cm3-sec and a maximum central temperature near 1200F.
Date: August 31, 1965
Creator: Arnold, J. L.; Miller, K. J. & Peterson, R. M.
Partner: UNT Libraries Government Documents Department
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The High-Temperature Irradiation Behavior of Hypostoichiometric Uranium Monocarbide

Description: From abstract: A series of three multi-compartmented experiments was designed to investigate the irradiation behavior uranium carbide fuels, as a function of composition, temperature, and burn-up; and the mechanical properties of Type 304 stainless steel, as a function of temperature and integrated thermal neutron flux.
Date: August 31, 1965
Creator: Hahn, R. D.
Partner: UNT Libraries Government Documents Department
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Thermal Studies Hastelloy X Metallic Insulation

Description: Hastelloy X wire wool has been considered by the Architect Engineer for exterior thermal insulation of some pipe sections of the ATR* gas loop. Heart transfer studies were made simulating gas loop operating conditions. This report describes the apparatus used and the resultant data. The insulation (manufactured by a commercial supplier) is of interest because of its corrosion resistance, strength, and ability to withstand impact and abrasion. Also, it is not a source of chlorides. The insulatio… more
Date: August 1, 1965
Creator: Hickerson, JP
Partner: UNT Libraries Government Documents Department
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Engineering Properties of Nuclear Craters, Report 3: Review and Analysis of Available Information on Slopes Excavated in Weak Shales

Description: This report provides information about slope stability problems which will arise if a new canal is excavated through the types of weak shale encountered along the present Panama Canal. It includes a discussion about the general problem and possible approaches, a review of previous experience, and a description of the new study.
Date: August 1965
Creator: Hirschfeld, R. C.; Whitman, Robert V. & Wolfskill, Lyle Anthony
Partner: UNT Libraries Government Documents Department
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Core Insulation Thermal Test

Description: The Core Insulation Development Program was initiated to investigate characteristics of pyrotile insulation as to bow, structural integrity, and thermal gradient when subjected to reactor temperatures and bundling pressures. Other forms of core insulation were to be tested at they become available.
Date: August 1, 1965
Creator: Kiefer, K.P.
Partner: UNT Libraries Government Documents Department
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